OOIR: Observatory of International Research

Papers

(The median citation count of Science and Technology of Nuclear Installations is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2021-05-01 to 2025-05-01.)

Article	Citations
Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions	34
Study on Probabilistic Safety Goals for Multimodule High-Temperature Gas-Cooled Reactor Based on Chinese Societal Risks	13
Prediction of the Loss of Feed Water Fault Signatures Using Machine Learning Techniques	10
Investigation of Oxidation and Counter-Oxidation in a One-Quarter Circular Geometry due to Shadow Corrosion	9
Integrity Evaluation of a Reactor Pressure Vessel Based on a Sequential Abaqus-FRANC3D Simulation Method	8
Effect of Inhomogeneous Mechanical Properties on the Stress-Strain Field at the Crack Tip and Crack Growth Direction in Dissimilar Metal Welded Joints	8
Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library	6
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	6
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	6
Research on Channel Modeling and Communication Coverage of Wireless Sensor Networks in Barrier Area of Nuclear Power Plants	6
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants	6
Development of an Integrated Human Error Simulation Model in Nuclear Power Plant Decommissioning Activities	5
Nuclear Waste Management: A Mini Review on Waste Package Characterization Approaches	5
Technical Options and Cost Estimates for Spent Nuclear Fuel Management at the Barakah Nuclear Power Plants	5
Detection of Illegal Movement in Radioactive Material Transportation Security Systems	5
Rapid Determination of Gross Alpha/Beta Activity in Water Based on Reverse Osmosis Membrane Enrichment Pretreatment	5
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger	4
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump	4
Optimization of the n/γ Pulse Shape Discrimination Performance of Plastic Scintillator Coupled With SiPM Arrays	4
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA	4
Development and Experimental Validation for Quantifying the Moisture Carryover in a Moisture Separator Using an Air/Water Test Facility	4
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model	4
Mechanical Properties Evaluation and Crack Propagation Behavior in Dissimilar Metal Welded Joints of 304 L Austenitic Stainless Steel and SA508 Low-Alloy Steel	4
Prediction of Crack Propagation Directions in Dissimilar Metal‐Welded Joints Using Phase‐Field Models and Discussion of Its Mechanisms	4
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process	4

Prediction of Automatic Scram during Abnormal Conditions of Nuclear Power Plants Based on Long Short-Term Memory (LSTM) and Dropout	3
Inerting Strategy for a Demonstration-Scale Hot Cell Facility Based on Experiences from Pilot-Scale Argon Cell Facility Operation and CFD Analysis	3
Assessment of Cesium Compound Behavior during Simultaneous Failure of Reactor Pressure Vessels and Spent Fuel Pools Using Modified ART Mod 2: Fukushima Daiichi Accident Simulation	3
Enhancing Radiation Shielding with Gadolinium(III) Oxide in Cerium(III) Fluoride‐Doped Silica Borate Glass	3
The Advancement of Neutron Shielding Materials for the Storage of Spent Nuclear Fuel	3
A Data-Driven Fault Prediction Method for Nuclear Power Systems Based on End-to-End Deep Learning Framework	3
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	3
Failure Fraction Calculation of the TRISO-Coated Particle Using X-Ray Computed Tomography	3
Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment	3
Assessment of Computational Technicalities for 2D/1D Coupling Method and Its Comparison with 3D MOC	3
An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes	3
Exponential Response Matrix Spectral Nodal Method for the Discrete Ordinates Neutral Particle Transport Model	3
Research on Radionuclide Diffusion Mechanism in the Ocean and Emergency Response under Oceanic Radioactive Events	2
Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel	2
Studying Disturbance Wave Velocity and Wall Shear Stress of Vertical Upward Annular Flow in Narrow Rectangular Channel	2
Interaction of Mechanical Heterogeneity and Residual Stress on Mechanical Field at Crack Tips in DMWJs	2
Analysis of the Effect of Applied Load on Crevice Corrosion Behavior	2
Thermomechanical Analysis of a Reactor Pressure Vessel under Pressurized Thermal Shock Caused by Inadvertent Actuation of the Safety Injection System	2
The Study of Dosimetric Characteristics of the XHA600D Medical Linear Accelerator Based on a Monte Carlo Code	2
Effect of Chloride Ions on Electrochemical Behavior of Canister Materials	2
Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material	2
Study on Airborne Radionuclide Dispersion in Floating Nuclear Power Plant under the Loss-of-Coolant Accident	2
Accuracy Evaluation of Monte Carlo Simulation Results Using ENDF/B‐VIII.0 and JENDL‐5 Libraries for 10 MW_th Micro Heat Pipe‐Cooled Reactor	2
High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment	2
COMSOL Simulation for Design of Induction Heating System in VULCAN Facility	2
Control Rod Modeling and Worth Calculation for a Typical 1100 MWe Nuclear Power Plant Using WIMS/D4 and CITATION	2
A Hybrid Method to Predict the Remaining Useful Life of Scroll Wheel of Control Rod Drive Mechanism	2
Methods for Predicting the Minimum Temperature of the Outage Loop and the Maximum Power Caused by the Low-Temperature Coolant	2
Integrated Security System (ISS) Design and Evaluation for Commercial Nuclear Power Plant	2
Machine Learning-Based Approach for Hydrogen Economic Evaluation of Small Modular Reactors	2
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall	1
Acceptable Level of Acceptance and the Affecting Factors: What Is the Acceptable Public Acceptance of Building a Nuclear Power Plant	1
Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM	1
Verification of the Efficacy of Passive Autocatalytic Recombiners in a Typical Pressurized Water Reactor under a Station Blackout Condition	1
Assessing the Impact of Common Cause Failures on Site Risk within Level 1 Multi-Unit PSA	1
Uranium Recovery from Phosphates for Self-Sufficient Nuclear Power in the Eastern Mediterranean	1
Deep Learning–Based Fault Identification Testing Experiment for Bellows Valves	1
Study on Missing Data Filling Algorithm of Nuclear Power Plant Operation Parameters	1
Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite	1
Influence of Weak Compressibility on the Hydrodynamic Performance Evaluation of Pump Turbines in the Pump Mode	1
Advancing Small Modular Reactor Technology Assessment in the Czech Republic, Egypt, and Poland	1
Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management	1
Nuclear Power Sustainability Path for China from the Perspective of Operations	1
A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem	1
	1
The Concept of the Heat Removal System of a High-Flux Research Reactor	1
Design Change and Operational Consideration of the HVAC System during Nuclear Power Plant Decommissioning	1
	1
Design of Control System of Once-Through Steam Generator Based on Proximal Policy Optimization Algorithm	1
A Novel Transformer‐Based Anomaly Detection Model for the Reactor Coolant Pump in Nuclear Power Plants	1

Effect of Photomultiplier Tube Voltage on the Performance of Sealed NaI (Tl) Scintillator Detectors	1
Research and Implementation of SVDU Simulator Based on Emulation Technology	1
Studies on Optimal Strategy to Adopt Nuclear Power Plants into Saudi Arabian Energy System Using MESSAGE Tool	1
Development of Fuel Product Barrier Monitoring System Based on State Functions in State-Oriented Emergency Operating Procedure	1
Study on the Applicability of Neutron Radiation Damage Method Used for High-Temperature Superconducting Tape Based on Geant4 and SRIM	1
Quantitative Assessment of Gaseous Effluents during Routine Operation: A Comparative Study of Planned Nuclear Power Plants at Lubiatowo‐Kopalino and Pątnów Sites in Poland	1
Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation	1
Application of EDG AOT Extension Based on the Risk-Informed Method in NPPs	1
Research and Analysis on Assembly Methodology for the Fusion Blanket System	1
Innovative Design of Compact Heavy-Load Independent Transfer Device for Nuclear Engineering System	1
Simulation of Ionizing/Displacement Synergistic Effects on NPN Bipolar Transistors Irradiated by Mixed Neutrons and Gamma Rays	1
Study on the Dispersion of Radionuclides under Different Hydrological Conditions of Spent Fuel Shipping in Daya Bay	1